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MONTHYEARML20096C6401984-08-27027 August 1984
Forwards Application to Amend License NPF-3,revising Tech Specs to Reflect Changes in Reactor Vessel Matls Irradiation Surveillance Schedule & Flow Verification of Auxiliary Feedwater Sys
Project stage: Request
ML20096C6631984-08-27027 August 1984
Application for Amend to License NPF-3,revising Tech Specs to Reflect Changes in Reactor Vessel Matls Irradiation Surveillance Schedule & Flow Verification of Auxiliary Feedwater Sys.Fee Paid
Project stage: Request
ML20096C6821984-08-27027 August 1984
Proposed Tech Specs Reflecting Changes in Reactor Vessel Matls Irradiation Surveillance Schedule & Flow Verification of Auxiliary Feedwater Sys
Project stage: Other
ML20101N4281984-12-11011 December 1984
Amend 79 to License NPF-3,changing Tech Spec Table 3.6-2 Re Containment Isolation Valve to Allow for Modified Steam Generator Blowdown & Drain Sys
Project stage: Other
ML20101N4481984-12-11011 December 1984
Safety Evaluation Supporting Amend 79 to License NPF-3
Project stage: Approval
ML20100A7681985-03-21021 March 1985
Submits Info Re Property Insurance Coverage,Per 10CFR50.54(w)(4) Requirements
Project stage: Request
ML20117L5491985-05-0909 May 1985
Informs That Response to 850321 Request for Addl Info Re Redundant Safety Features Actuation Signal Channel Independence Will Be Submitted in Jul 1985
Project stage: Request
ML20133D7961985-08-0101 August 1985
Responds to Re NUREG-0737,Item II.E.1.1 Concerning Auxiliary Feedwater Sys Tech Specs & Request to Review SER & Submit Revised Amend Application.Revised Application Will Be Submitted by 850830
Project stage: Other
ML20138C9801985-08-29029 August 1985
Proposed Tech Spec Changes,Identifying Water Source for Auxiliary Feedwater Pumps,Safety Grade Flow Indication Used for Flow Verification & Bases
Project stage: Other
ML20138C9731985-08-29029 August 1985
Application for Amend to License NPF-3,identifying Water Source for Auxiliary Feedwater Pumps,Safety Grade Flow Indication for Flow Verification & Bases
Project stage: Request
ML20138C9651985-08-29029 August 1985
Forwards Application for Amend to License NPF-3,revising Tech Specs Re Water Source for Auxiliary Feedwater Pumps, Safety Grade Flow Indication for Flow Verification & Bases
Project stage: Request
ML20212C8791986-12-22022 December 1986
Safety Evaluation Supporting Amend 96 to License NPF-3
Project stage: Approval
ML20212C8351986-12-22022 December 1986
Amend 96 to License NPF-3,modifying Tech Spec Sections 3.7.1.2 & 4.7.1.2 & Associated Bases to Clarify Applicability of Limiting Condition for Operation & to Add New Surveillance Requirements for Auxiliary Feedwater Sys
Project stage: Approval
ML20215L8391987-05-0404 May 1987
Proposed Tech Specs Re Auxiliary Feedwater Sys Surveillance Requirement 4.7.1.2d
Project stage: Other
ML20215K3801987-05-0404 May 1987
Requests Reissuance of Table 3.6-2, Containment Isolation Valves of Tech Spec 3/4.6.3,correcting Typos in 840911 Application to Amend License NPF-3
Project stage: Request
ML20215L8351987-05-0404 May 1987
Application for Amend to License NPF-3,deleting Portion of Tech Spec Surveillance Requirement 4.7.1.2d Re Auxiliary Feedwater Sys as Result of 850609 Loss of Feedwater Event. Supporting Documentation Encl
Project stage: Request
ML20215L8141987-05-0404 May 1987
Forwards Application for Amend to License NPF-3,deleting Portion of Tech Spec Surveillance Requirement 4.7.1.2d to Reflect Mods to Steam Line Piping to Auxiliary Feed Pump Turbine Following 850609 Loss of Feedwater Event.Fee Paid
Project stage: Request
ML20216H6041987-06-25025 June 1987
Advises That Based on B&W Analytical Studies for Primary Sys Blowdown Using RELAP5,use of Blowdown Valves Not Practicable for Feed & Bleed,Per 851204 Commitment.Listed Proposed Mods Will Be Implemented to Enhance Makeup Sys
Project stage: Other
ML20236G9801987-10-27027 October 1987
Application for Amend to License NPF-3,revising Tech Spec Section 3/4.3.2, Safety Sys Instrumentation, Table 3.3-5 & Section 3/4.6.3, Containment Isolation Valves, Table 3.6-2 to Support Enhanced Feed & Bleed Mods.Fee Paid
Project stage: Request
ML20236H0211987-10-27027 October 1987
Proposed Tech Specs,Changing Section 3/4.3.2, Safety Sys Instrumentation, Table 3.3-5 & Section 3/4.6.3, Containment Isolation Valves, Table 3.6-2 to Support Enhanced Feed & Bleed Mods
Project stage: Other
ML20236Y3421987-12-0808 December 1987
Forwards Application for Amend to License NPF-3,revising Tech Spec 4.6.1.2c.3,Section 3/4.6.1.2 Re Containment Sys & Containment Leakage.Fee Paid
Project stage: Request
ML20237A6881987-12-0808 December 1987
Informs of Changes Necessary to Support Fifth Refueling Outage in Feb 1988.Key Amend Requests Placed Into 1 of 3 Listed Categories.Nrc Should Allocate Necessary Resources to Provide Timely Support for Review & Issuance of Amends
Project stage: Other
ML20150B0321988-03-0707 March 1988
Forwards Application for Amend to License NPF-3 Changing Tech Spec Section 4.6.1.2.a to Allow Third Type a Test & 10-yr Inservice Insps to Be Uncoupled & Performed in Separate Refueling Outages.Fee Paid
Project stage: Request
ML20148B1781988-03-14014 March 1988
Amend 110 to License NPF-3,revising Tech Specs to Permit Extension of Range of RCS Pressure Instrument on Auxiliary Shutdown Panel to 3,000 Psig from 2,500 Psig & Tech Spec 3.3.3.5,Table 3.3-9,Item 3
Project stage: Other
ML20151X2411988-04-29029 April 1988
Forwards Discussion of & Proposed Revs to Tech Specs for Resolution of NRC Comments Concerning Deletion of Auxiliary Feedwater Pump Turbine Inlet Steam Pressure Interlock Operability Requirements,Per 880406 Telcon
Project stage: Other
1986-12-22
[Table View] |
Text
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Mb ;. TOLEDO
%s EDISON RcMano P. Caouse v.c. %sant Docket No. 50-346
%.,9w, License No. NPF-3 Serial No. 1074 August 27, 1984 Director of Nuclear Reactor Regulation Attention:
Mr. John F. Stolz Operating Reactor Branch No. 4 Division of Operating Reactors United States Nuclear Regulatory Commission Washington, DC 20555
Dear Mr. Stolz:
Under separate cover, we are transmitting three (3) original and forty (40) conformed copics of an application for Amendment to Facility Operating License No. NPF-3 for the Davis-Besse Nuclear Power Station Unit No. 1.
This application requests that the Davis-Besse Nuclear Power Station Unit 1 Technical Specifications, Appendix A, be revised to reflect the changes attached. The proposed changes include:
1.
Section 4.4.9.1.2, Table 4.4-5 and Bases 2.
Section 4.7.1.2 The two attachments identify the proposed changes and its safety evaluation and significant hazard consideration.
Item 1 concerns revision to the Reactor Vessel Materials Irradiation Surveillance Schedule to reflect the change in operating cycle length. The change is from 12 to 18 month refueling, cycle with anticipated reduction in accumulated neutron fluence of the reactor vessel material. Also, the revised schedule will reduce unnecessary handling of dummy capsules which will reduce personnel exposure.
Item 2 concerns the flow verification of the Auxiliary l
Feedwater System after an extended outage (>30 days in Mode 5), refueling outages (every 18 months) or modification to the system that could affect the system.
It also requires verification of locked valve position and when testing is being performed which requires valve realignment, a dedicated individual will be stationed at the valves with communication to the control room who will restore the system to the required line up if l
l necessary.
60 I(p 8409050368 840827 I
g y8ut I
PDR ADOCK 05000346 i
P PDR y
THE TOLEDO EDISON COMPANY EDISON PLAZA 300 MADISON AVENUE TOLEDO. OHIO 43652
,,-.c y
-This amendment request involves two requests. Enclosed is a check for
$300 as requested by 10CFR170.12.
.Very truly yours, Attachment ec: DB-1 NRC Resident Inspector State of Ohio e
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